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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
Darryl D. Siemer
Nuclear Technology | Volume 178 | Number 3 | June 2012 | Pages 341-352
Technical Note | Reprocessing | doi.org/10.13182/NT12-A13599
Articles are hosted by Taylor and Francis Online.
An often cited weakness of the Integral Fast Reactor (IFR) concept is that the chloride salt-based radioactive waste generated by its electrorefiner (ER) cannot be vitrified. Although that assertion is literally true, it is also misleading because it would be quite simple to recycle that waste's chloride and vitrify its cationic components (mostly alkali metals and fission products). Producing this alternative to Argonne National Laboratory's ceramic waste form would entail vitrification of a mixture of orthophosphoric acid, ferric oxide, and powdered ER salt with a melter able to efficiently disengage gas bubbles, e.g., a Stir Melter. The HCl evolved by this process would be absorbed by an aqueous lithium/potassium hydroxide scrub solution, which would then be dried and recycled as fresh ER electrolyte. Because radioiodide would otherwise accumulate in the ER salt, the caustic scrub solution would occasionally be contacted with cuprous or silver chloride before recycle. This scenario's primary advantages would be much lower cost and approximately fivefold greater effective waste loading. This paper describes the experimental work supporting these contentions.